ML20199L692

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Proposed Tech Specs Section 3/4.6.I,relocating from Chemistry TS Requirements to UFSAR
ML20199L692
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 01/21/1999
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20199L584 List:
References
NUDOCS 9901280098
Download: ML20199L692 (10)
v • d • e


Text

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]3 . TABLE OF CONTENTS TOC UMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

]' SECTION g i

t 3L4.6 PRIMARY SYSTEM BOUNDARY -

3/4.6.A Recirculation Loops . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4.6 '

4

)4 3/4.6.B . Jet Pumps ............................................ 3/4.6-:

3/4.6.C Recirculation Pum ps . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4.61

3,4.6.o i R.ci,oustion i.oop Sta, tup ................................ 3/4.6-4 l 3/4.6.E Safety Valves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4.6*.

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[f 3/4.6.F. Relie f Valves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4.6-1 '

3/4.6.G Leaksge Detection Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4.6-1(

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! 3/4.6.H Operational Leakage . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4.6 3/4.6.1 mi *

. J ................. 3/4.6-1:

T e 6.l , of m i .

3/4.6.J ' Specific Activity . $. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4. 6-11 l
3/4.6.K Pressure / Temperature Limits . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4.6-1!

, Figure 3.6.K-1, Pressure-Temperature Limits for Pressure Testing - Valid to 18 EFP' Figure 3.6.K-2, Pressure-Temperature Limits for Pressure Testing - Valid to 20 EFP' i

Figure 3.6.K-3, Pressure-Temperature Limits for Pressure Testing - Valid to 22 EPP' l

. Figure 3.6.K-4, Pressure-Temperature Limits for Non-Nuclear Heatup/Cooldown - Valid to 22 EFPY Figure 3.6.K-5, Pressure-Temperature Limits for Critical Core  ;

j Operations - Valid to 22 EFPY  ;

3/4.6.L Reactor Steam Dome Pressure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4.6 2:

3/4.6.M Mein Steam Line isolation Valves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4.6-2:

3/4.6.N Structural integrity . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4.6-24 '

3/4.6.0 Residual Heat Removal - HOT SHUTDOWN . . . . . . . . . . . . . . . . . . . . . . . 3/4.6-2!

3/4.6.P Residual Heat Removal - COLD SHUTDDWN . . . . . . . . . . . . . . . . . . . . . . 3/4.6-2; QUAD CITIES - UNITS 1 & 2 vill Amendment Nos. I 2 and :

9901290098 PDR ADOCK O990121 4[

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TABLE OF CONTENTS

. B TOC BASES SECTION f.691 3.L4J PRIMARY SYSTEM BOUNDARY 3/4.6.A' Recirculation Loops . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4.6-1 3/4.6.B Jet Pumps . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4.6-1 3/4.6.C Recirculation Pumps ..................................

B 3/4.6-1 3/4.6.D Idle Recirculation Loop Startup . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4.6-1 3/4.6.E Safety Valves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 3/4.6-3 3/4.6.F Relief Valves .......................................

B 3/4.6-3 3/4.6.G Leakage Detection Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4.6-3 3/4.6.H Operational Leakage

.................................. B 3/4.6-4 3 74 .6.i 3/4.6.J Q .-e.9.d5h 4........................... B 3/4.6-4 Specific Activity . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

B 3/4.6-5 3/4.6.K Pressure / Temperature Limits . . . . . . . . . . . . . . . . . . . . . .'. . . . . . . B 3/4.6 5 3/4.6.L Reactor Steam Dome Pressure ...........................

B 3/4.6 8 3/4.6.M Main Steam Line isolation Valves ......................... B 3/4.6 8 3/4.6.N. Structuralintegrity

................................... B 3/4.6-8 3/4.6.0 Residual Heat Removal - HOT SHUTDOWN . . . . . . . . . . . . . . . . . . . B 3/4.6-8 3!4.6.P Residual Heat Removal - COLD SHUTDOWN . . . . . . . . . . . . . . . . . . B 3/4.6 8 QUAD CITIES - UNITS 1 & 2 XXI Amendment Nos. maw

PRIMARY SYSTEM BOUNDARY 3/4.6.1 Tl/G CO/DITIO FORgPERAT)dN .6-S VEIL}dNCE QUljldMENT he istry I. hemi ry T ech istry the r ctorc ant Th eacto coola shall b etermi to yste shall main ined w' in th imits b withi he s cified c mistry li by:

s fiedin able .1 1.

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, /. APPL ABILI

1. ensur ont pri to press react during ch start , if not ing th i
po rmed w' in the pr ious I 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.

O RA NAL DE(s) 1, 2'd d 3'"

Analy ' g a som of the actor cool t for:

A ON:

. Chlori s at les once pe .

1. In PERA ONAL ODE :
1) 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> , and I
a. h the nduc ity, oride 3 oncen tion pH e eedi the 2) 8h rs who ver co ctivity limit cifie in Ta e 3.6.  ; is rester t n the li t in able 3. -1.

1 For 2 ho s duri one c inuo time ' terval, d b. or.*tucti y at les once s 72 hou .

21 For 6 ho s per ye for

[ co uctivi and chl ide c. pH t least o ce per 8 ours 1 ncent tion, an never nductiv' is gre r han the mit in T le 3.6.1 .

s mho/c at 25'C nd 3. ontinuo sly recor ing the nductivi ith the oride co entratio of the actor co ant, or, hen the 50.5 pp conti ous re rding co ductivity I m stor is in erable, btaining n in-  !

the co ion does ot need o be l' condu svity m suremen t least repo to the mmissi . nce per hours.

b. h the co uctivity hloride ,

oncentra n or pH xceedin the 7A,y j a Na Y8 * **

  • I I limit s fied in T le 3.6. ; bg
1) r >72 urs dur' g one le.N b { AJ kk continu s time i erval, or OJ:17:6L*p6:a";jfd;70;[M"'"""I**"d" ""dM "

QUAD CITIES - UNITS 1 & 2 3/4.6-13 Amendment Nos.

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PRIMARY SYSTEM BOUNDARY 3/4.6.1 3.6 M NG CO I ON[FOR O RATIO 4.6 QUIR ENTS[

2) or > 3 hours er year or 4. P orma e of a ANNE HECK cond tivity a chlori e con uousc ductivi monit con ntratio , with a in-line f w cell least ce por:

Be i t least TARTU within t e no 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> . a 7 day , and

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c. ith th conduc ity b. 2 ours w enever nducti is

>10 ho/cm t 25'C chlorid ater th the li in To con ntration 0.5 pp . , be in .6.1- 1.

I HOT UTDO within hours in C O SHUT OWN ithin t next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

2. OPER lONAL ODE (s) and 3 with t conduc ity, chl ide conc tration pH exc eding t limit spe fied in T le 3.6. 1 for

> 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> uring o conti ous tim terval, in at le HOT SHUTD N wit n the n 12 h rs and i COLD UTDO withi the foil ing 24 urs.

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I QUAD CITIES - UNITS 1 & 2 3/4.6 14 Amendment Nos. &W i i

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PRIMARY SYSTEM BOUNDARY B 3/4.6 4

. I i BASES Leakage from the reactor coolant pressure boundary inside the drywell is detected by at least one or two independently monitored vasiables, such as sump level changes and drywell atmosphere radioactivity levels. The means of quantifying lokage in the drywell is the drywell floor drain i sump pumps. With the drywell floor drain su;np pump system inoperable, no other form of monitoring can provide the equivalent information. However, primary containment atmosphere j sampling for radioactivity can provide indication of changes in leakage rates.

1

! 3/4.6.H Operational Leakaae I

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The allowable leakage rates from the reactor coolant system have been based on the predicted and '

experimentally observed behavior of cracks in pipes. The normally expected background leaksge l

i due to equipment design and the detection capability of the instrumentation for determining system leakage was also considered. The evidence obtained from experiments suggests that for leakage l somewhat greater than that specified for UNIDENTIFIED LEAKAGE the probability is small that the imperfection or crack associated with such leakage would grow rapidly. However, in all cases, if

,; the leakage rates exceed the values specified or the leakage is located and known 'to be PRESSURE i

BOUNDARY LEAKAGE, the reactor will be shutdown to allow further investigation and corrective action.

An UNIDENTIFIED LEAKAGE increase of more than 2 gpm within a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period is an indication of a potential flaw in the reactor coolant pressure boundary and must be quickly evaluated.

Although the increase does not necessarily violate the absolute UNIDENTIFIED LEAKAGE limit, IGSCC susceptible components must be determined not to be the source of the leakage within the  !

i required completion time.

Tbs S e c.3 s e a ide w Y t a d A N 8L \"

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! 3/4.6.1 hemist hLAdK  !

! T wat chemis limit of the r actor lant s tem ar stablis d to pr ent da age to t e ,

r ctor storial in cont t with e cool t. Chi ide lim' are s ified t prevent ress j orro n crac g of t staini s steel The et et of e oride is ot as g at who the oxy en l

! I con ntratio in the olent i ow, th the O ppm li it on c rides i permitt during WER O ATIO 3

onduct' ity me . ureme s are r uired a con uous b is sinc change in this remeter re an indi tion of bnorm condit' ns. W en the onducti ty is wi in limit , the pH chlorid an other' puriti affect' g cond etivity ust al be wit their ceptab limits. 6th the con etivity eter i perabl , additi al sam es mus be anal ed to e sure th the chi ides a I

no exc g the l' its. \

ction permit tempor ry ope tion w' chemi ry limit outside f the li its requ' in OPER IONA ODE witho requir' g Com ission n ificatio . The s veillanc requir ents prov' e adeq te ass rance at con ntratio in exc s of th limits w' be det ted in ufficient ti to tak correc e acti .

tri s QUAD CITIES - UNITS 1 & 2 8 3/4.6 4 Amendment Nos.

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, ATTACHMENT C SIGNIFICANT IIAZARDS CONSIDERATION

~ SVP-99-003 Page 1 of 2 Comed has evaluated this proposed amendment and has determined that it does not represent a significant hazards consideration. According to 10 CFR 50.92(c), a proposed amendment to an operating license involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not:

Involve a significant increase in the probability of occurrence or consequences of an accident previously evaluated; Create the possibility of a new or different kind of accident from any previously analyzed; or involve a significant reduction in a margin of safety.

Comed proposes to relocate, to administrative controls, the chemistry limits provided in Technical Specifications Section 3/4.6.I, Primary System Boundary - Chemistry.

The determination that the criteria set forth in 10 CFR 50.92 is met for this amendment request is indicated below:

Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?

The proposed changes simplify the TS, meet regulatory requirements for relocated TS's, and implement the recommendations of the Commission's Final Policy Statement on TS improvements. The Chemistry requirements will be relocated to the Updated Final Safety Analysis Report (UFSAR) and to applicable station procedures. Future changes to these requirements will be controlled by 10 CFR 50.59. The proposed changes are administrative in nature and do not involve any modification to any plant equipment or affect plant operation. Therefore, the proposed changes do not involve a significant increase in the probability or consequences of any previously evaluated accident.

Consequently, this proposed amendment does not involve a significant increase in the probability or consequences of any accident previously evaluated.

, i.-

. ATTACHMENT C SIGNIFICANT HAZARDS CONSIDERATION

. SVP-99-003 Page 2 of 2 Does the change create the possibility of a new or different kind of accident from any accident previously evaluated?

The proposed changes are administrative in nature, do not involve any physical alterations to any plant equipment, and cause no change in the method by which any safety related system performs its function. Therefore, this proposed TS amendment will not create the possibility of a new or different kind of accident from any accident previously evaluated.

Does the change involve a significant reduction in a margin of safety?

The proposed amendment represents the relocation of current requirements which are based on generic guidance or previously approved provisions for other stations.

The proposed changes are administrative in nature and do not adversely affect ,

existing plant safety margins or the reliability of the equipment assumed to operate '

in the safety analysis. The proposed changes have been evaluated and found to be acceptable for use at Quad Cities Nuclear Power Station. Since the proposed changes are administrative in nature, and are based on NRC accepted provisions which have been adopted at other nuclear facilities, and maintain the necessary levels of system reliability, the proposed changes do not involve a significant reduction in the margin of safety.

Therefore, based upon the above evaluation, Comed has concluded that these changes do not constitute a significant hazards consideration.

. O

~% i

, ATTACIIMENT D ENVIRONMENTAL ASSESSMENT

, , SVP-99-003 Page1 of1 l

Comed has evaluated this proposed operating license amendment request against the I criteria for identification oflicensing and regulatory actions requiring environmental l assessment in accordance with 10 CFR 51.21. Comed has determined that this proposed license amendment request meets the criteria for a categorical exclusion set forth in 10 CFR 51.22(c)(9) and as such, has determined that no irreversible consequences exist in accordance with 10 CFR 50.92(b). This determination is based on the fact that this change is being proposed as an amendment to a license issued pursuant to 10 CFR 50 that changes a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or that changes an inspection or a surveillance requirement, and the amendment meets the following specific criteria:

l (i) The amendment involves no significant hazards consideration.

As demonstrated in Attachment C, this proposed amendment does not involve any significant hazards consideration.

l (ii) There is no significant change in the types or significant increase in the amounts of any effluent that may be released offsite.

The proposed change is administrative in nature. There will be no change in the types or significant increase in the amounts of any effluents released offsite.

(iii) There is no significant increase in individual or cumulative occupational radiation exposure. I The proposed changes will not result in changes in the operation or configuration of the facility. There will be no change in the level of controls or methodology used for processing of radioactive effluents or handling of solid radioactive waste, nor will the proposal result in any change in the normal radiation levels within the plant. Therefore, there will be no increase in individual or cumulative occupational radiation exposure resulting from this change.

. k.

STATE OF ILLINOIS Docket Nos. 50-254 50-265 IN TIIE MATTER OF:

I COMMONWEALTil EDISON (COMED) COMPANY QUAD CITIES NUCLEAR POWER STATION - UNITS I & 2 AFFIDAVIT l 1

i I affirm that the content of this transmittal is true and correct to the best of my I

knowledge, information and belief. I r}/)_ ov/ -

oel P. Dimmette, J

)

Site Vice Presiden l Quad Cities Station I l

l 1

Subscribed and sworn to before me, a Notary Public in and  !

for the State above named, this J/ day of Yawunev ,19 99.

l L1 _L L AvtJ.'

L '

Notary Public "OFFIC4AL SEAL" UNDALEESTOERMER Notary Putsc, State ofinnois i

3 E ..:. . ~ ! ? " "

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